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Experiment requirements for the study of anticipated transients with and without scram. [BWR; PWR]

Technical Report ·
OSTI ID:6494116
;
Characteristics of anticipated transients with and without scram in light water reactors are reviewed. Fuel rod behavior during the most significant events is typified by pellet-cladding-interaction and cladding collapse. A program to simulate selected transients in the Power Burst Facility (PBF) so as to evaluate and understand the fuel behavior in light water reactors is proposed. Experiment requirements are set forth and the capabilities and limitations of the PBF to perform these tests are outlined.
Research Organization:
Idaho National Engineering Lab., Idaho Falls (USA)
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
6494116
Report Number(s):
TFBP-TR-308
Country of Publication:
United States
Language:
English

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